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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Robert P. Schuman
Nuclear Technology | Volume 65 | Number 3 | June 1984 | Pages 422-431
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT84-A33398
Articles are hosted by Taylor and Francis Online.
Two leach-resistant waste forms, a borosilicate glass developed for the high-level waste calcines from reprocessed uranium fuels and iron-enriched basalt, a fused ceramic developed for americium plus plutonium wastes, have been leach tested. The specimens were leached in distilled deionized water and in a saturated salt brine at ∼30°C for 28, 63, and 126 days; one set was leached in a gamma field of ∼104 Gy/h (∼106 rad/h). The specimens were simulated high-level waste forms prepared from inactive ingredients and spiked with 22Na, 60Co, 95Zr-95Nb, 137Cs, 133Ba, 144Ce, and 241Am. The components were melted and heat treated, and specimens were sawed from the solidified material. The gamma field increased the leach rates in water (pH ∼3 after irradiation) typically by a factor of ∼10 and increased the leach rates in salt brine (pH decreased much less during irradiation) by a factor of ∼2. The leach rate of cobalt from glass was about seven times that from iron-enriched basalt. The leach rates usually decreased with increasing leach time. Both waste forms were still leach resistant in irradiated brine at 30°C, <2 µg/cm2·day, and fairly leach resistant in irradiated water at 30°C, <25 µg/cm2·day.